ML16134A676
| ML16134A676 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/11/1982 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16134A675 | List: |
| References | |
| NUDOCS 8208240237 | |
| Download: ML16134A676 (25) | |
Text
- . -.-- ----- --
Attachment 1 Duke Power Company Oconee Nuclear Station Proposed Technical Specification Revision Oconee 3, Cycle 7 Pages 2.1-2 3.5-20 2.1-3b 3.5-20a 2.1-3d 3.5-20b 2.1-6 3.5-20c 2.1-9 3.5-20d 2.1-12 3.5-20e 2.3-10 3.5-23 3.2-2 3.5-23a 3.5-9 3.5-23b 3.5-17 3.5-26 3.5-17a 3.5-26a 3.5-17b 3.5-26b 820 bZ40911
can be related to DNB through the use of the BAW-2 correlation (1). The BAW-2 correlation has been developed to predict DNB and the location of DNB for axially uniform and non-uniform heat flux distributions. The local DNB ratio (DNBR), defined as the ratio of the heat flux that would cause DNB at a particular core location to the actual heat flux, is indicative of the margin to DNB. The minimum value of the DNBR, during steady-state operation, normal operational transients, and anticipated transients is limited to 1.30. A DNBR of 1.30 corresponds to a 95 percent probability at a 95 percent confidence level that DNB will not occur; this is considered a conservative margin to DNB for all operating conditions. The difference between the actual core outlet pressure and the indicated reactor coolant system pressure has been considered in determining the core protection safety limits. The difference in these two pressures is nominally 45 psi; however, only a 30 psi drop was assumed in reducing the pressure trip setpoints to correspond to the elevated location where the pressure is actually measured.
The curve presented in Figure 2.1-1A represents the conditions at which a minimum DNBR of 1.30 is predicted for the maximum possible thermal power (112 percent) when four reactor coolant pumps are operating (minimum reactor coolant flow is 106.5 percent of 131.3 x 106 lbs/hr). This curve is based on the combination of nuclear power peaking factors, with potential effects of fuel densification and rod bowing, which result in a more conservative DNBR than any other shape that exists during normal operation.
The curves of Figure 2.1-2A are based on the more restrictive of two thermal limits and include the effects of potential fuel densification and rod bowing:
- 1. The 1.30 DNBR limit produced by the combination of the radial peak, axial peak and position of the axial peak that yields no less than a 1.30 DNBR.
- 2. The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.05 kw/ft for Unit 1.
Power peaking is not a directly observable quantity and therefore limits have been established on the bases of the reactor power imbalance produced by the power peaking.
The specified flow rates of Figure 2.1-3A correspond to the expected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.
The curve of Figure 2.1-1A is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3A.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup dependent DNBR rod bow penalty for the ap plicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis. All plant operating limits are based on a minimum DNBR criteria of.1.30 plus the amount necessary to offset the reduction in DNBR due to fuel rod bow.
2.1-2
- 1. The 1.30 DNBR limit produced by the combination of the radial peak, axial peak and position of the axial peak that yields no less than a 1.30 DNBR.
- 2. The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.15 kw/ft for Unit 2.
Power peaking is not a directly observable quantity, and, therefore, limits have been established on the bases of the reactor power imbalance produced by the power peaking.
The specified flow rates 2.1-3B correspond to the expected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.
The curve of Figure 2.1-1B is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup dependent DNBR rod bow penalty for the ap plicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis. All plant operating limits are based on a minimum DNBR criteria of 1.30 plus the amount necessary to offset the reduction in DNBR due to fuel rod bow. (3)
The maximum thermal power for three-pump operation is 90.606 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.08 =
80.68 percent power plus the maximum calibration and instrument error. The maximum thermal power for other coolant pump conditions are produced in a similar manner.
For each curve of Figure 2.1-3B, a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The curve of Figure 2.1-1B is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
References (1) Correlation of Critical Heat Flux in.a Bundle Cooled by Pressurizer Water, BAW-10000, March 1970.
(2) Oconee 2, Cycle 4 - Reload Report, BAW-1491, August 1978.
(3) Oconee 2, Cycle 6 - Reload Report, BAW-1691, August 1981.
2.1-3b
- 2. The combination of radial and axial peak that causes central fuel melting at the hot spot. The limits for Unit 3 are 20.5 kw/ft for fuel rod burn up less than or equal to 10,000 MWD/MTU and 21.5 kw/ft - after 10,000 MWD/MTU.
Power peaking is not a directly observable quantity, and, therefore, limits have been established on the bases of the reactor power imbalance produced by the power peaking.
The specified flow rates of Figure 2.1-3C correspond to the expected minimum flow rates with four pumps., three pumps, and one pump in each loop, respectively.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup dependent DNBR rod bow penalty for the ap plicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis. All plant operating limits are based on a minimum DNBR criteria of 1.30 plus the amount necessary to offset the reduction in DNBR due to.fuel rod bow. (4)
The maximum thermal power for three-pump operation is 90.65 percent due to a power level trip produced by the flux-flow ration 74.7 percent flow x 1.08 =
80.7 percent power plus the maximum calibration and instrument error (Reference 4). The maximum thermal power for other coolant pump conditions are produced in a similar manner.
For each curve of Figure 2.1-3C a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The curve of Figure 2.1-1C is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3C.
References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000, March 1970.
(2) Oconee 3, Cycle 3 - Reload Report - BAW-1453, August 1977.
(3) Amendment 1 - Oconee 3, Cycle 4 - Reload Report - BAW-1486, June 12, 1978.
(4) Oconee 3, Cycle 7*- Reload Report - DPC-RD-.2001, Revision 1, July 1982.
2.1-3d
2400 ACCEPT4 BLE OPERAT ON 2200-- ..
u 2000 00 UNACCPTABLE OPERA'ION 580 600 620 640 660 Reactor Coolant Core Outlet Temperature,oF CORE PROTECTION SAFETY LIMITS UNIT 3 DUKfwow OCONEE NUCLEAR STATION Figure 2.1-1C 2.1-6
THERMAL POWER LEVEL,%
Ml =0.529 -120
(-32.5,112.0) (33.0,112.0)
M2= -1.864
'ACCEPTABLE
(-49.5,103.0) 4PUMP
(-32.5 90.64) (33.0, 0.64).
ACCEPTABLEI
(-49.5,81.64) 1 3 & 4 PUMP -80 (49.5,81.25)
OPERATION
(-32. 63.26) (33.0163.26)
I-60 1 (49.5,59.89) 1 ACCEPTABLEI
(-49.5,54.76) I 2,3, & 4 PUMP I OPERATIONI I -40 S(49.5,32.51)
-20 I ~I
-60 -40 -20 20 40 60 REACTOR POWER IMBALANCE;%
CORE PROTECTION SAFETY LIMITS UNIT 3 unwEPOW OCONEE NUCLEAR STATION Figure 2.1-2C 2.1-9
2400 ACCEPTABLE /
OPERATION /
2200 Z/
4 PUMP 2000
/ 2PUMP D 3PUMP /
UNACCEPTABLE OPERATION 1600 580 600 620 640 660 Reactor Coolant Core Outlet Temperature, OF PUMPS COOLANT POWER TYPE OF LIMIT OPERATING FLOW (GPM) (% FP) 4 374,880(100%) 112.0 DNBR 3 280,035(74.7%) 90.7 DNBR 2 183,690(49.0%) 63.63 DNBR/QUALITY CORE PROTECTION SAFETY LIMITS DDL UNIT 3 owa OCONEE NUCLEAR STATION Figure 2.1-3C 2.1-12
THERMAL POWER LEVEL,%
Ml = 0.755
(-10.5,108.0) (16.5,108.0) M2= -1.89 ACCE TABLE4 IPUMP CPERATION1 I-100
(-33.5,90.6)
(-10.5,80.6) (16. 80.6)
(33.5,75.9)
I4CCEPI ABLE 3 & 4 1PUMP OPERATION
(-33.5,63.2)
I -60
(-10.5,52.9) (16.5152.9)
ApCEPTA BLE 2,3, & 4 (33.5,48.5)
PUMP CPERATIONI I- 40
(-33.5,35.5)
-20 (33.5,20.8)
I I__ _ _ _ _ _ _ _ _ _ _
I __________I ____
-60 -40 -20 20 40 60 REACTOR POWER IMBALANCE,% PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNIT 3 ouIrown OCONEE NUCLEAR STATION Figure 2.3-2C 2-3-10
Bases The high pressure injection system and chemical addition system provide con trol of the reactor coolant system boron concentra.tion.(1) This is normally accomplished by using any of the three high pressure injection pumps in series with a boric acid pump associated with either the boric acid mix tank or the concentrated boric acid storage tank. An alternate method of boration will be the use of the high pressure injection pumps taking suction directly from the borated water storage tank.(2)
The quantity of boric acid in storage in the concentrated boric acid storage tank or the borated water storage tank is sufficient to borate the reactor coolant system to a 1% Ak/k subcritical margin at cold conditions (70oF) with the maximum worth stuck rod and no credit for xenon at the worst time in core life. The current cycles for each unit were analyzed with the most limiting case selected as the basis for all three units. Since only the present cycles were analyzed, the specifications will be re-evaluated with each reload. A minimum of 1020 ft3 of 8,700 ppm boric acid in the concentrated boric acid storage tank, or a minimum of 350,000 gallons of 1835 ppm boric acid in the borated water storage tank (3) will satisfy the requirements. The volume re quirements include a 10% margin and, in addition, allow for a deviation of 10 EFPD in the cycle length. The specification assures that two supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a cold condition. The required amount of boric acid can be added in several ways. Using only one 10 gpm boric acid pump taking suction from the concentrated boric acid storage tank would require approximately 12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to inject the required boron. An alternate method of addition is to inject boric acid from the borated water storage tank using the makeup pumps.
The required boric acid can be injected in less than six hours using only one of the makeup pumps.
The concentration of boron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, and to assure a flow of boric acid is available when needed, these tanks and their associated piping will be kept at least 100 F above the crystallization temperature for the concentration present. The-boric acid concentration of 8,700 ppm in the concentrated boric acid storage tank cor responds to a crystallization temperature of 770 F and therefore a temperature requirement of 870 F. Once in the high pressure injection system, the concen trate is sufficiently well mixed and diluted so that normal system temperatures assure boric acid solubility.
REFERENCES (1) FSAR, Section 9.1; 9.2 (2) FSAR, Figure 6.2 (3) Technical Specification 3.3 3.2-2
- f. If the maximum positive quadrant power tilt exceeds the Maximum Limit of Table 3.5-1, the reactor shall be shut down within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Subsequent reactor operation is permitted for the purpose of measurement, testing, and corrective action provided the ther mal power and the Nuclear Overpower Trip Setpoints allowable for the reactor coolant pump combination are restricted by a reduc tion of 2% of thermal power for each 1% tilt for the maximum tilt observed prior to shutdown.
- g. Quadrant power tilt shall be monitored on a minimum frequency of once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during power operation above 15% full power.
3.5.2.5 Control Rod Positions
- a. Technical Specification 3.1.3.5 does not prohibit the exercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.
- b. Except for physics tests, operating rod group overlap shall be 25% +/- 5% between two sequential groups. If this limit is ex ceeded, corrective measures shall be taken immediately to achieve an acceptable overlap. Acceptable overlap shall be attained within two hours or the reactor shall be placed in a hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c. Position limits are specified for regulating and-axial power shaping control rods. Except for physics tests or exercising control rods, the regulating control rod insertion/withdrawal limits are specified on figures 3.5.2-lAl, 3.5.2-1A2, and 3.5.2-1A3 (Unit 1); 3.5.2-1B1, 3.5.2-12, and 3.5.2-1B3 (Unit 2); 3.5.2-1i1, 3.5.2-1C2, and 3.5.2-1C3 (Unit 3) for four pump operation, on figures 3.5.2-2A1, 3.5.2-2A2, and 3.5.2-2A3 (Unit 1); 3.5.2-2B1, 3.5.2-2B2, and 3.5.2-2B3 (Unit 2); figures 3.5.2-2C1, 3.5.2-2C2, and 3.5.2-2C3 (Unit 3) for three pump operation, and on figures 3.5.2-2A4, 3.5.2-2A5, and 3.5.2-2A6 (Unit 1); 3.5.2-2B4, 3.5.2-2B5, and 3.5.2-2B6 (Unit 2); figures 3.5.2-2C4, 3.5.2-2C5, and 3.5.2-2C6 (Unit 3) for two pump operation. Also, excepting physics tests or exercising control rods, the axial power shaping control rod insertion/withdrawal limits are specified on figures 3.5.2-4A1, 3.5.2-4A2, and 3.5.2-4A3 (Unit 1); 3.5.2-4B1, 3.5.2-4B2, and 3.5.2-4B3 (Unit 2); 3.5.2-4C1, 3.5.2-4C2, and 3.5.2-4C3 (Unit 3).
If the control rod position limits are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position. An acceptable control rod position shall then be attained within two hours. The minimum shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.
3.5-9
POWER LEVB1 (300,102) 100- (150,102) CUTOFF-100% FP 8 0,L .
(275.92) 80 SHUTDOWN (270,80)
MARGIN LIMIT RESTRICTED OPERATION
~.60 Lw UNACCEPTABLE OPERATION 190,50). (200,50)
ACCEPTABLE OPERATION 20 (40,15) (90,15)
(0,5h(
0 50 100 150 200 250 300 ROD INDEX,%WD 0 25 50 75 100 BANK5 0 ?5 50 75 100 BANK 6 0 25 50 75 100 BANK 7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 50 (+1o, -0) EFPD UNIT 3 oUErowni OCONEE NUCLEAR STATION Figure 3.5.2-I11 3.5-17
POWER LEVEL (275,102) ( ,
100. (150,102)
CUTOFF=100% FP SHUTDOWN (260,92)
MARGIN LIMIT (250,80)
RESTRICTED OPERATION UNACCEPTABLE 60 OPERATION (90,50) (200,50) 40 ACCEPTABLE OPERATION 20.
(40,15) (90,15)
(0,10)
(0.5) 0 50 100 150 200 250 300 ROD INDEX.%WO 0 25 50 75 100 BANK5 0 25 50 75 100 BANK6 0 25 50 75 100 BANK7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 50 (+10, -0) TO 200 (+10) EFPD UNIT 3 UKEPOWl OCONEE NUCLEAR STATION Figure 3.5.2-102 3.5-17a
POWER LEVEL CUTOFF=100% FP (275 (3 00 ,102) 10 0 -
220,102) 275 02)
(260,92) 80 -(250,80)
UNACCEPTABLE OERACTO OPERATIONOPRTN 60 (160,50) (200,50)
Q 40 wi SHUTDOWN ACCEPTABLE MARGIN S- OPERATION LIMIT 20 (100,15)
(0,5) 0 I 0 50 100 150 200 250 300 ROD INDEX,%WD 0 25 50 75 100 BANK5 0 25 50 75 100 BANK6 25 50 75 100 BANK7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION AFTER 200 (+1O) EFPD CUNIT 3
Orom OCONEE NUCLEAR STATION Figure 3.5.2-1C3 3.5-17b
100 (130,77) (263,77) (300,77 so UNACCEPTABLE OPERATION RESTRICTED (90,50) OPERATION (200,50) 40 SHUTDOWN
-.-.- .MARGIN .ACCEPTABLE LIMIT OPERATION 20 (30,15) (90,15 (0,10) 0 0 50 100 150 200 250 300 ROD INDEX,%WD 0 25 50 75 100 BANK5 0 25 50 75 100 BANK6 0 25 50 75 100 BANK7 ROD POSITION LIMITS FOR THREE-PUMP OPERATION FROM 0 TO 50 (+]0, -0) EFPD UNIT 3
,DUKE70WR OCONEE NUCLEAR STATION Figure 3.5.2-201 3.5-20
1001 80 (300,77)
(130,77) (245,77)
UNACCEPTABLE
>60. OPERATION 3: REST RICTED 2 OPERATION (90,50)
(200,50)
~40 SHUTDOWN MARGIN LIMIT ACCEPTABLE OPERATION 20 (30, 15) (90,1T5)
(0 ,10)
(0,5)e 0 50 100 150 200 250 300 ROD INDEX,%WD 0 25 50 75 100 BANK 5 0 25 50 75 100 BANK 6 0 25 50 75 100 BANK7 ROD POSITION LIMITS FOR THREE-PUMP OPERATION FROM 50 (+10, -0) TO 200 +1o EFPD UNIT 3 DuK[ow[R) OCONEE NUCLEAR STATION Figure 3.5.2-2C2 3.5-20a
100 RESTRICTED
/OPERATION 80(210,77)
/ 4 (300,77)
(160.50)
UNACCEPTABLE (200,50)
OPERATION L 40 SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 (100, 15)
(0,5) 0 50 100 150 200 250 300 ROD INDEX,%WD 0 25 50 75 100 BANK5 0 25 50 75 100 BANK6 0 25 50 75 100 BANK7 ROD POSITION LIMITS FOR THREE-PUMP OPERATION AFTER 200 110 EFPD UNIT 3 un Pow! OCONEE NUCLEAR STATION Figure 3.5.2-2C3 3.5-20b
100L 80 080,52)
(200,50) 0 LIATACETAL SHUTOPERTIO OPRTO NAEPTABLEABL OPERATONRAIO OPER TION (50,15) (90,15)
(0.10)
(0,5) 0 50 100 150 200 250 300 ROD INDEX.%,WD 0 25 50 75 . 100 BANK 5 0 25 50 75 100 BANK 6 0 25 50) 75 100 BANK7 ROD POSITION LIMI.TS FOR TWO-PUMP OPERATION FROM 0 TO 50 (C+10, -0) EFPD UNIT 3 0UOWn OCONEE NUCLEAR STATION Figure 3.5.2-2CI; 3.5-20c
_ _-- -p---
100 804 60 LU 8 (0,2)(203.52) (300,52)
Q.
(200,50) 0 40 SHUTDOWN .RESTRICTED MARGIN OPERATION ACCEPTABLE LIMIT OPERATION 20* UNACCEPTABLE
.OPERATION f5,15 9,5 (0 ,10)
(0,5) 0 0 50 100 150 200 250 300 ROD INDEXWD 0 25 50 75 100 BANK5 0 25 50 75 100 BANK 6 0 25 50 75 100 BANK7 ROD POSITION.LIMITS FOR TWO-PUMP OPERATION FROM 50 (+10, -0) TO 200 +10 EFPD UNIT 3 DUKEPOwR OCONEE NUCLEAR STATION Figure 3.5.2-2,5 3 .- 20d
- l 100*
80 RESTRICTED OPERATION 0
3: 17 52 (203.52) 1300,52 UNACCEPTABLE OPERATION
~40 lw SHUTDOWN ACCEPTABLE MARGIN OPERATION LIMIT 20 (110,15)
(0,5) 0 0 50 100 150 200 250 300 ROD INDEX,%WD 0 25 50 75 100 BANK 5 0 25 50 75 100 BANK 6 0 25 50 75 10 I'I I BANK7 ROD POSITION LIMITS. FOR TWO-PUMP OPERATION AFTER 200 +10 EFPD UNIT 3
( ow\IOCONEE P NUCLEAR STATION Figure 3.5.2-2C6 3.5-20e
REACTOR POWER,%FP
(-22.2,102.0) 100 (25.0,102.0)
(-24.5,92.0) ACCEP ABLE (30.0,92.0)
OPER TION
(-30.0,80.0) 80 60 RESTRICTED OPERATION RESTRICTED OPERATION 40 20
-100 -80 -60 -40 -20 0 20 40 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 TO 50 (+10, -0) EFPD UNIT 3 DUEPOWE~ OCONEE NUCLEAR STATION Figure 3.5.2-3Cl 3.5-23
REACTOR POWER,%FP
(-28.3,102.0) - 100 (25.0,102.0)
ACCEP ABLE
(-30.0,92.0) A A (30.0,92.0)
OPER TION
-80 60 RESTRICTED OPERATION RESTRICTED OPERATION 20
-100 -80 -60 -40 -20 0 20 40 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE FROM 50 (+10, -0) TO 200 i10 EPD UNIT 3 puEPOWER) OCONEE NUCLEAR STATION Figure 3.5.2-3C2 3.5-23a
REACTOR POWER,%FP
(-30.0,102.0) (25.0,102.0)
-100
(-35.0,92.0) ACCE ABLE (30.0,92.0)
OPERATION
-80 60 RESTRICTED OPERATION RESTRICTED OPERATION
- 40 20
-100 -80 -60 -40 -20 0 20 40 60 80 100 IMBALANCE,%
OPERATIONAL POWER IMBALANCE ENVELOPE 6ou. AFTER 200 +10 EFPD UNIT 3 OCONEE NUCLEAR STATION Figure 3.5.2-3C3 3.5-23b
I 100 loo
- (10,102) 1(40,102) 1012 (6.0,92) 80o (0,80) . 140,80)
RESTRICTED OPERATION U
~60 660 C)
ACCEPTABLE OPERATION
< 40-(100,40) 20 0 20 40 60 80 100 APSR POSITION.%WD APSR POSITION4 LIMITS FOR OPERATIONJ FROMi 0 TO 200 -10 EFPD UNIT 3 kowri OCONEE NUCLEAR STATION Figure 3.5.2-4c]
3 5-26
(10.0, 102) -(39.0, 102) 100 (6.0,92) 80 (0,830) (40,80)
RESTRICTED OPERATION U. C-)
~60 60 - .(60,60)
U 0
C ACCEPTABLE OPERATION (100,40) 20 0 20 40 60 80 100 APSR POSITIONWD APSR POSITION L!MITS FOR OPERATION AFTER 200 +10 EFPD UN IT 3 ur[pown OCONEE NUCLEAR STATION Figure 3.5.2-4c2 3.5-26a
Figure 3.5.2-4C3 Deeed during Oconee Unit 3,Cycle 7 Operation